<?xml version="1.0" encoding="UTF-8"?><?xml-stylesheet type="text/xsl" href="static/style.xsl"?><OAI-PMH xmlns="http://www.openarchives.org/OAI/2.0/" xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xsi:schemaLocation="http://www.openarchives.org/OAI/2.0/ http://www.openarchives.org/OAI/2.0/OAI-PMH.xsd"><responseDate>2026-09-19T18:44:45Z</responseDate><request verb="GetRecord" identifier="oai:dspace.mit.edu:1721.1/77064" metadataPrefix="dim">https://dspace.mit.edu/server/oai/request</request><GetRecord><record><header><identifier>oai:dspace.mit.edu:1721.1/77064</identifier><datestamp>2022-01-13T07:54:37Z</datestamp><setSpec>com_1721.1_7582</setSpec><setSpec>com_1721.1_7581</setSpec><setSpec>col_1721.1_131024</setSpec></header><metadata><dim:dim xmlns:dim="http://www.dspace.org/xmlns/dspace/dim" xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xmlns:doc="http://www.lyncode.com/xoai" xsi:schemaLocation="http://www.dspace.org/xmlns/dspace/dim http://www.dspace.org/schema/dim.xsd">
   <dim:field mdschema="dc" element="contributor" qualifier="advisor" lang="en_US">Dennis Whyte.</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="author" lang="en_US">Drenkhahn, Robert (Robert A.)</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="other" lang="en_US">Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering.</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="department">Massachusetts Institute of Technology. Department of Nuclear Science and Engineering</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="accessioned">2013-02-14T19:14:54Z</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="available">2013-02-14T19:14:54Z</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="issued" lang="en_US">2012</dim:field>
   <dim:field mdschema="dc" element="identifier" qualifier="uri">http://hdl.handle.net/1721.1/77064</dim:field>
   <dim:field mdschema="dc" element="identifier" qualifier="oclc" lang="en_US">824454660</dim:field>
   <dim:field mdschema="dc" element="description" lang="en_US">Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012.</dim:field>
   <dim:field mdschema="dc" element="description" lang="en_US">"June 2012." Cataloged from PDF version of thesis.</dim:field>
   <dim:field mdschema="dc" element="description" lang="en_US">Includes bibliographical references (p. 31-32).</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="abstract" lang="en_US">Thorium-based fuels for nuclear reactors are being considered for use with current and future designs in both large and small-scale energy production. Thorium-232 is as abundant on Earth as lead, far more common than all isotopes of uranium, leading to its greatly reduced cost. Thorium itself offers a significantly greater neutron absorption cross-section than uranium at thermal energies, resulting in greater efficiency and smaller geometries. Certain thorium-based fuels can also significantly reduce proliferation by denaturing the thorium fuel cycle product U-233 (which is cause for proliferation concern) with U-236 and U-238. Several countries, including the USA, China, and India, are developing new conceptual designs which focus on the advantages offered by thorium. Thorium reactor technology today, as well as its practicality in the near-future, was surveyed to determine its potential for a major role in the nuclear power industry. Factors considered were economics, efficiency, waste, and proliferation. It is recommended that thorium-based fuels be further integrated in future reactor designs to take advantage of its numerous benefits in these areas.</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="statementofresponsibility" lang="en_US">by Robert Drenkhahn.</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="degree" lang="en_US">S.B.</dim:field>
   <dim:field mdschema="dc" element="format" qualifier="extent" lang="en_US">33 p.</dim:field>
   <dim:field mdschema="dc" element="language" qualifier="iso" lang="en_US">eng</dim:field>
   <dim:field mdschema="dc" element="publisher" lang="en_US">Massachusetts Institute of Technology</dim:field>
   <dim:field mdschema="dc" element="rights" lang="en_US">M.I.T. theses are protected by 
copyright. They may be viewed from this source for any purpose, but 
reproduction or distribution in any format is prohibited without written 
permission. See provided URL for inquiries about permission.</dim:field>
   <dim:field mdschema="dc" element="rights" qualifier="uri" lang="en_US">http://dspace.mit.edu/handle/1721.1/7582</dim:field>
   <dim:field mdschema="dc" element="subject" lang="en_US">Nuclear Science and Engineering.</dim:field>
   <dim:field mdschema="dc" element="title" lang="en_US">Critical assessment of thorium reactor technology</dim:field>
   <dim:field mdschema="dc" element="type" lang="en_US">Thesis</dim:field>
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   <dim:field mdschema="others" element="access-status">unknown</dim:field>
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	&lt;Type xmlns="https://www.openaire.eu/cerif-profile/vocab/COAR_Publication_Types">http://purl.org/coar/resource_type/c_1843&lt;/Type>
	&lt;Language>eng&lt;/Language>
   	&lt;Title>Critical assessment of thorium reactor technology&lt;/Title>
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   	&lt;PublicationDate>2012&lt;/PublicationDate>
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        	&lt;DisplayName>Drenkhahn, Robert (Robert A.)&lt;/DisplayName>
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            &lt;DisplayName>Massachusetts Institute of Technology&lt;/DisplayName>
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    &lt;License>http://dspace.mit.edu/handle/1721.1/7582&lt;/License>
    &lt;Keyword>Nuclear Science and Engineering.&lt;/Keyword>
   	&lt;Abstract>Thorium-based fuels for nuclear reactors are being considered for use with current and future designs in both large and small-scale energy production. Thorium-232 is as abundant on Earth as lead, far more common than all isotopes of uranium, leading to its greatly reduced cost. Thorium itself offers a significantly greater neutron absorption cross-section than uranium at thermal energies, resulting in greater efficiency and smaller geometries. Certain thorium-based fuels can also significantly reduce proliferation by denaturing the thorium fuel cycle product U-233 (which is cause for proliferation concern) with U-236 and U-238. Several countries, including the USA, China, and India, are developing new conceptual designs which focus on the advantages offered by thorium. Thorium reactor technology today, as well as its practicality in the near-future, was surveyed to determine its potential for a major role in the nuclear power industry. Factors considered were economics, efficiency, waste, and proliferation. It is recommended that thorium-based fuels be further integrated in future reactor designs to take advantage of its numerous benefits in these areas.&lt;/Abstract>
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